燃料包壳

M5锆合金主要应用于核反应堆堆芯的燃料包壳和结构件。

M5 zirconium alloy is mainly applied in the nuclear reactor core as the fuel cladding tubes and structure materials .

通过堆外模拟试验，研究了国产316－Ti不锈钢包壳管在4种氧势下对FCCI（燃料包壳化学相互作用）和FPLME（裂变产物液态金属脆化效应）的敏感性。

The susceptibility of domestic 316-Ti stainless steel cladding tube with respect to Fuel Cladding Chemical interaction ( FCCI ) and Fission Products - induced Liquid Metal Embrittlement ( FPLME ) under four oxygen POtentials has been investigated by out-of-pile simulation test .

用于超临界水堆燃料包壳的ODS铁素体钢的研究进展

Progress of Using Oxide Dispersion Strengthened Ferritic Steels as Fuel Cladding Materials in Supercritical Water Reactor

本文提出利用热处理工艺改善再结晶退火态M5锆合金的组织和性能，旨在提高核燃料包壳的寿命，为促进核燃料包壳国产化提供一定的理论参考和依据。

In order to extend the life of nuclear fuel cladding tubes , this paper proposes to improve microstructure and properties by heat treatment of M5 zirconium alloys on recrystallization annealing state .

基于LOFTL2-5试验的一维与三维计算结果比较，初步分析了有关三维效应及其对ECC旁通等应急堆芯冷却过程以及燃料包壳峰值温度（PCT）的影响。

By comparing the 1-D and 3-D calculation results of LOFT L2-5 test progress , related 3-D effects and its influence on such emergency core cooling progress as ECC bypass etc and that on the fuel peaking cladding temperature ( PCT ) is preliminarily investigated .

反应堆冷却剂部分丧失时燃料包壳完整性分析方法

Analysis Method for the Fuel Cladding Integrality during Partial Loss of Reactor Coolant

用于原子能反应堆燃料包壳管探伤和测量的电脑化多通道超声工作系统

Computerized Multi-channel Supersonic Working System for Defect Detection and Measurement of Fuel Sheathing Tubes for Atomic Reactors

这给我们的启示是如果要发展超临界水堆核燃料包壳用锆合金，那么除了需要解决耐腐蚀性能以外，吸氢问题应给予更大关注。

This indicates that if the development of advanced zirconium alloy for fuel cladding used in supercritical water reactors is considered , the issue of hydrogen uptake should be given more attention , in addition to improving corrosion resistance of zirconium alloys . 9 .

热处理对U3Si2－Al燃料板包壳显微组织及其厚度测量的影响

The Effect of Heat-Treatment on the Microstructure and Thickness Measurement of Cladding for U_3Si_2-Al Fuel Plates

用MCNP程序计算核燃料废包壳缓发裂变中子形成的热中子通量密度

Computing with MCNP the thermal flux density due to the delayed fission neutron generated in processing the clads of burned-up fuel roads

M5合金是一种适用于高燃耗组件的新型锆合金，主要用作燃料棒包壳、端塞、导向管和定位格架材料。

M5 alloy was a new zirconium alloy used in high burn up assembly such as fuel cladding , end plug , guide tube and grid spring and so on .

国内池式轻水研究反应堆中，尽管其燃料元件包壳材料、反应堆水池覆面材料和主要堆内构件材料以及运行温度不一样，其冷却剂pH值都定为偏酸性。

Although the materials of nuclear fuel cladding , internal surface and the main reactor internals , and operating temperatures of the pool type light water reactors in China are different from each other . All of pH value of water in the pools are always selected as slight acidity .

一种用于退役核燃料元件包壳的破裂检测技术

A safety check-up method for decommissioned reactor fuel element cladding

聚变-裂变混合堆包层燃料元件包壳热应力的初步研究

The thermal stresses study for blanket fuel element cladding of fusion-fission hybrid reactor

核燃料棒包壳泄漏探测器

Nuclear fuel rod sheath leak detector

中国先进研究堆燃料元件包壳候选材料中温动水腐蚀

Middle temperature dynamic water side corrosion of fuel cladding of Al alloys for China Advanced Research Reactor

事故瞬态过程中的燃料元件包壳的热点温度是评价反应堆安全的重要参数。

Fuel-pin cladding temperature under accident cases is an important parameter in evaluating the safety of the reactor .

堆芯损伤状态包括堆芯无损伤、燃料元件包壳破损、燃料过热和燃料熔化等四种。

Core damage states include no core damage , fuel clad failure , fuel overheat and fuel melt .

无缝燃料元件包壳管

Seamless fuel clad tube

国产快堆燃料元件包壳材料316不锈钢的中子辐照效应

The Effects of Neutron Irradiation on the Type 316 Stainless Steel for Homemade Fast Reactor Fuel Element Cladding Material

在反应堆运行过程中，堆功率的波动和水冷却介质的流动会导致燃料元件包壳局部承受反复的循环变形，极端情况下会导致疲劳失效。

In practical application , it is subjected to local plastic strain cycles due to the power fluctuations during reactor operation ;

锆合金具有独特的耐腐蚀性能和良好的机械性能，常作为核燃料的包壳。

Zirconium alloy which is often used as nuclear fuel cladding tube has a unique corrosion resistance and good mechanical properties .

燃料棒包壳是反应堆放射性物质的第一道屏障，它能包容90%以上的裂变产物。

The fuel rod cladding is the first shield against radioactive material , which can accept more than 90 % of fission product .

本课题研究一个以缓发中子法监测为主，总法和裂变气体法监测为辅的三元法燃料元件包壳破损数字化监测仪。

The thesis makes a research on three-dimensional fuel element cladding damage digital monitor with delayed neutron monitoring as the major method and general γ and fission gas monitoring as the minor method .

锆合金作为轻水核反应堆燃料元件的包壳材料已得到了广泛的应用并积累了丰富的经验，因而仍被列为SCWR潜在的应用材料。

As a light water nuclear reactor fuel cladding material , Zr alloy has been wide used and its application experience accumulated , hence it is the potential materials for SCWR .

核反应堆燃料元件铝包壳温度测量

Temperature measurements of the aluminium claddings of fuel elements in nuclear reactor

核燃料元件棒包壳管自动切管机的研制

Development of automatic tube cutting machine for cladding tube of nuclear fuel element

氧化物燃料与不锈钢包壳的化学相互作用&一种半经验公式的导出

Oxide Fuel and Stainless Steel Cladding Chemical Interaction ( FCCI ) & Deducing of a Semiempirical Equation

锆合金被广泛应用于核反应堆中，作为燃料元件的包壳材料或堆内结构部件，织构会影响其众多的应用性能，因此织构的研究及控制在锆合金的开发利用中具有重要作用。

Zirconium alloys are generally employed as structural components and fuel cladding in nuclear reactors . The texture influences many application properties of zirconium alloy .

这些方法有利于加深理解燃料芯块、包壳和结构部件的辐照行为，为提高燃耗提供依据。

These methods contribute to understand irradiation behavior of fuel , cladding and structure components and supply proof for increasing burnup .